聚变第一壁自钝化W-Cr-Zr合金氧化层结构与氧化行为

doi:10.11901/1005.3093.2024.211

材料研究学报 DOI: 10.11901/1005.3093.2024.211

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聚变第一壁自钝化W-Cr-Zr合金氧化层结构与氧化行为

吴玉程¹,左彤¹,谭晓月¹,²,朱晓勇¹,刘家琴¹

1. 合肥工业大学
2.

Oxide Layer Structure and Oxidation Behaviors of Self-Passivated W-Cr-Zr Alloys Facing First Wall in Fusion

1.
2. Hefei University of Technology

引用本文:

吴玉程左彤谭晓月朱晓勇刘家琴. 聚变第一壁自钝化W-Cr-Zr合金氧化层结构与氧化行为[J]. 材料研究学报, 10.11901/1005.3093.2024.211.

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摘要: 自钝化钨合金（Self-Passivating Tungsten Alloy，SPTA）能够在表面形成致密氧化物，从而抑制其进一步氧化。因此自钝化钨合金用作核聚变第一壁材料是针对未来核聚变装置发生冷却失水事故可能面临的安全隐患而提出的材料解决方案。自钝化钨合金表面形成的致密氧化物需要钝化元素的参与，发生氧化行为与其组成和结构相关。本文以自钝化W-Cr-Zr合金为研究对象，采用3D激光测量显微镜、扫描电子显微镜（SEM）和X射线衍射仪（XRD）表征其氧化前后表面粗糙度、形貌和物相组成等，探究氧化层结构对W-Cr-Zr合金后续氧化行为的影响。结果表明，表面粗糙度越大，材料在氧化初期形成的氧化层上的裂纹越多；在后续的氧化过程中，裂纹作为氧与基体接触的通道，加速基体氧化，从而具备较大的线性氧化速率。W-Cr-Zr合金氧化生成的氧化层最表面为高温稳定性的Cr2WO6，亚表层为易升华的WO2.83；当氧化层去除Cr2WO6层后，在后续的氧化过程中伴随着基体的严重氧化和WO2.83的迅速升华，仍能形成一较疏松的Cr2WO6层，具有一定的抗氧化性能。控制自钝化钨合金的组织结构和氧化行为对于核聚变装置部件材料选择和运行安全具有重要参考价值。

关键词 ：核聚变, W-Cr-Zr合金, 表面粗糙度, 初始表面氧化层, 氧化行为

Abstract：Self-passivating tungsten alloy (SPTA) inhibits further oxidation by forming dense oxides on its surface. Therefore, the use of self-passivating tungsten alloy as the first wall material for nuclear fusion is a material solution proposed to address the safety hazards that may arise in the event of loss-of coolant accident in future nuclear fusion devices. The compact oxide formed on the surface of self-passivating tungsten alloy requires the participation of passivating elements, and the oxidation behavior is related to its composition and structure. The surface roughness, morphology and phase composition of self-passivating W-Cr-Zr alloy before and after oxidation were characterized by 3D laser measurement microscopy, scanning electron microscope (SEM) and X-ray diffraction instrument (XRD), and the influence of oxide layer structure on the subsequent oxidation behavior of W-Cr-Zr alloy was investigated. The results show that the larger the surface roughness, the more cracks on the oxide layer formed in the initial oxidation stage. In the subsequent oxidation process, cracks act as the contact channel between oxygen and matrix to accelerate the oxidation of matrix, thus having a large linear oxidation rate. The most surface of the oxide layer formed by the oxidation of W-Cr-Zr alloy is Cr2WO6 with high temperature stability, and the subsurface is WO2.83 with easy sublimation. After the removal of Cr2WO6 layer, a relatively loose Cr2WO6 layer can still be formed in the subsequent oxidation process along with the severe oxidation of the matrix and the rapid sublimation of WO2.83, which has certain anti-oxidation performance. Controlling the microstructure and oxidation behavior of self-passivating tungsten alloy is of great reference value for material selection and operation safety of nuclear fusion device components.

Key words： Nuclear Fusion, W-Cr-Zr alloy, Surface roughness, Initial surface layer, Oxidation behavior

收稿日期: 2024-05-16

ZTFLH:

TL34

基金资助:国家自然科学基金国际（地区）合作与交流重点项目;国家重大研发计划;高等学校学科创新引智计划“清洁能源新材料与技术”

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https://www.cjmr.org/CN/Y0/V/I/0

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